Comparative thermo-hydraulic study of different nuclear spent fuel cask designs using CFD codes-Reference-Cited by-同舟云学术

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Comparative thermo-hydraulic study of different nuclear spent fuel cask designs using CFD codes

Published:2023-11 Issue: Volume:192 Page:110006
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Hernandez-Avellaneda Andres^ORCID,Jimenez Gonzalo^ORCID,Rey Luis^ORCID,Martinez-Murillo Juan Carlos

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference27 articles.

1. Calculation chain for the analysis of spent nuclear fuel in long-term interim dry storage;Arkoma;Ann. Nucl. Energy,2018

2. Methodology for thermal analysis of spent nuclear fuel dry cask using CFD codes;Benavides;Ann. Nucl. Energy,2019

3. Spent nuclear fuel;Bruno;Elements,2006

4. Procedure for estimation and reporting of uncertainty due to discretization in CFD applications;Celik;J. Fluids Eng.,2008

5. The TN-24P PWR spent-fuel storage cask testing and analyses;Creer,1987

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